Author:
Breslavsky Dmytro,Tatarinova Oksana
Publisher
Springer Nature Switzerland
Reference33 articles.
1. Brumovsky M (2018) Evaluation of Reactor Internals Integrity and Lifetime According to the NTD ASI. In: Proceedings of the ASME 2018 Pressure Vessels and Piping Conference, Pressure Vessels and Piping Conference, vol 1A: Codes and Standards
2. Chopra OK (2010) Degradation of LWR core internal materials due to neutron irradiation. Argonne National Laboratory, NRC Job Code N6818, Office of Nuclear Regulatory Research
3. Lee KH, Park JS, Ko HO, Jhung MJ (2013) Analysis for aging and operating experiences of reactor vessel internals. In: Transactions of the Korean Nuclear Society Autumn Meeting Gyeongju, KNS, Daejon
4. Ma BM (1983) Nuclear Reactor Materials and Applications. Iowa State University
5. Zinkle SJ, Tanigawa H, Wirth BD (2019) Chapter 5 - radiation and thermomechanical degradation effects in reactor structural alloys. In: Odette GR, Zinkle SJ (eds) Structural Alloys for Nuclear Energy Applications, Elsevier, Boston, pp 163–210
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